Home / Publications / Journals / Nuclear Science and Engineering / Volume 81

Volume 81

Number 1 | Number 2 | Number 3 | Number 4

Number 1

Table of Contents
J. Robert Oppenheimer, Shatterer of Worlds(Alvin M. Weinberg)

Comments on the Formulation of the One-Dimensional Six-Equation Two-Phase Flow Model

G. Le Coq, J. Lewi, P. Raymond

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 1-8

Technical Paper / dx.doi.org/10.13182/NSE82-A19590

Code Assessment by a Two-Phase Nozzle Flow Experiment

Frank Kedziur

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 9-22

Technical Paper / dx.doi.org/10.13182/NSE82-A19591

Uncertainty Analysis of Time-Dependent Nonlinear Systems: Theory and Application to Transient Thermal Hydraulics

J. Barhen, D. G. Cacuci, J. J. Wagschal, M. A. Bjerke, C. B. Mullins

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 23-44

Technical Paper / dx.doi.org/10.13182/NSE82-3

On the Energy and Momentum Deposition in the Ion Beam-Pellet Interaction

S. Cuperman, B. Levush

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 45-54

Technical Paper / dx.doi.org/10.13182/NSE82-A19593

Sensitivity of Computed Uranium-238 Self-Shielding Factors to the Choice of the Unresolved Average Resonance Parameters

J. L. Munoz-Cobos, G. de Saussure, R. B. Perez

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 55-65

Technical Paper / dx.doi.org/10.13182/NSE82-A19594

A Modified Wigner Rational Approximation for Neutron Collision Escape Probability from Bare Homogeneous Reactor Assemblies

Anil Kumar

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 66-74

Technical Paper / dx.doi.org/10.13182/NSE82-A19595

Conserving Average Rate of Energy Loss in Transport Calculations for Light Charged Particles

D. E. Cullen, S. T. Perkins

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 75-91

Technical Paper / dx.doi.org/10.13182/NSE82-A19596

Numerical Analysis of the Boltzmann Equation Including Fokker-Planck Terms

K. Przybylski, J. Ligou

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 92-109

Technical Paper / dx.doi.org/10.13182/NSE82-A19597

Asymptotic Equivalence of Neutron Diffusion and Transport in Time-Independent Reactor Systems

Mieczysłew Borysiewicz, Janusz Mika, Giampiero Spiga

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 110-118

Technical Paper / dx.doi.org/10.13182/NSE82-A19598

Binary Operators and Their Green's Functions

James R. Sheff

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 119-136

Technical Paper / dx.doi.org/10.13182/NSE82-A19599

Neutron Diffusion in Graphite Poisoned with 1/v and Non-1/v Absorbers

U. Malik, L. S. Kothari, A. Kumar

Nuclear Science and Engineering / Volume 81 / Number 1 / May 1982 / Pages 137-143

Technical Note / dx.doi.org/10.13182/NSE82-A19600

Number 2

Table of Contents
Energy, The Conservation Revolution(H. G. MacPherson)
Transitional Energy Policy 1980–2030 Alternative Nuclear Technologies(Hugh F. Henry)
itle:ESN(Bruce R. Wienke)
An Evaluation of ENDF/B-IV and Hansen-Roach Uranium-233 Cross Sections for Use in Criticality Calculations(S. R. McNeany, J. D. Jenkins)

An Equivalence Relation for a Doubly Heterogenous Lattice

M. Segev

Nuclear Science and Engineering / Volume 81 / Number 2 / June 1982 / Pages 151-160

Technical Paper / dx.doi.org/10.13182/NSE82-A20082

Measurements of Neutron and Gamma-Ray Streaming in a Cavity-Duct System and an Analysis by an Albedo Monte Carlo Method

Kazuo Shin, Ryuji Murakami, Hiroaki Taniuchi, Tomonori Hyodo, Yoshiaki Oka

Nuclear Science and Engineering / Volume 81 / Number 2 / June 1982 / Pages 161-171

Technical Paper / dx.doi.org/10.13182/NSE82-A20083

Effect of Fluorescence, Bremsstrahlung, and Annihilation Radiation on the Spectra and Energy Deposition of Gamma Rays in Bulk Media

K. V. Subbaiah, A. Natarajan, D. V. Gopinath, D. K. Trubey

Nuclear Science and Engineering / Volume 81 / Number 2 / June 1982 / Pages 172-195

Technical Paper / dx.doi.org/10.13182/NSE82-A20084

Absolute Measurement of the Uranium-235 Fission Cross Section from 0.2 to 1.2 MeV

Oren A. Wasson, Michael M. Meier, Kenneth C. Duvall

Nuclear Science and Engineering / Volume 81 / Number 2 / June 1982 / Pages 196-212

Technical Paper / dx.doi.org/10.13182/NSE82-A20085

New Calculation of Prompt Fission Neutron Spectra and Average Prompt Neutron Multiplicities

David G. Madland, J. Rayford Nix

Nuclear Science and Engineering / Volume 81 / Number 2 / June 1982 / Pages 213-271

Technical Paper / dx.doi.org/10.13182/NSE82-5

An Extension of the Nodal Green's Function Method for Reactor Analysis

Chang Yu-Man, L. M. Grossman, P. L. Chambré, B. S. Lew

Nuclear Science and Engineering / Volume 81 / Number 2 / June 1982 / Pages 272-280

Technical Note / dx.doi.org/10.13182/NSE82-A20087

Statistical Screening of Input Variables in a Complex Computer Code

Theodore J. Krieger

Nuclear Science and Engineering / Volume 81 / Number 2 / June 1982 / Pages 281-283

Technical Note / dx.doi.org/10.13182/NSE82-A20088

Derivation of a Dose Mean Value of Lineal Energy from Variance Measurements of a Secondary Electron Emission Current

B. Forsberg

Nuclear Science and Engineering / Volume 81 / Number 2 / June 1982 / Pages 283-290

Technical Note / dx.doi.org/10.13182/NSE82-A20089

KINE—A One-Dimensional Dynamics Program for Pressurized Water Reactors with Partial Boiling in the Core

R. Fiebig, A. Krüger

Nuclear Science and Engineering / Volume 81 / Number 2 / June 1982 / Pages 291-298

Technical Note / dx.doi.org/10.13182/NSE82-A20090

A Note on Estimation of Pressure Sensor Time Constant from the Normal Operating Data

S. M. Wu, M. S. Ouyang

Nuclear Science and Engineering / Volume 81 / Number 2 / June 1982 / Pages 298-299

Technical Note / dx.doi.org/10.13182/NSE82-A20091

Number 3

Table of Contents
STP(F. Aguilar, P. G. Tuttle, A. C. Hutter)
Nuclear and Radiochemistry(Vincent P. Guinn)
Nuclear Reactor Engineering(Andrew Robeson)
Nuclear Reactor Safety Heat Transfer(P. A. Lottes)

Interfacial Exchange Relations for Two-Fluid Vapor-Liquid Flow: A Simplified Regime-Map Approach

J. E. Kelly, M. S. Kazimi

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 305-318

Technical Paper / dx.doi.org/10.13182/NSE82-A20276

Wall Heat Transfer Coefficient for Condensation and Boiling in Forced Convection of Sodium

H. C. No, M. S. Kazimi

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 319-324

Technical Paper / dx.doi.org/10.13182/NSE82-A20277

Neutron and Gamma-Ray Doses at Hiroshima and Nagasaki

W. E. Loewe, E. Mendelsohn

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 325-350

Technical Paper / dx.doi.org/10.13182/NSE82-A20278

Subcritical Limits for Uranium-235 Systems

Hugh K. Clark

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 351-378

Technical Paper / dx.doi.org/10.13182/NSE82-A20279

Subcritical Limits for Uranium-233 Systems

Hugh K. Clark

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 379-395

Technical Paper / dx.doi.org/10.13182/NSE82-A20280

The Isomeric Ratio in Thermal and Fast Neutron Capture of Americium-241

K. Wisshak, J. Wickenhauser, F. Käppeler, G. Reffo, F. Fabbri

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 396-417

Technical Paper / dx.doi.org/10.13182/NSE82-6

Cesium-133 Neutron Capture Cross Section

R. L. Macklin

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 418-422

Technical Paper / dx.doi.org/10.13182/NSE82-A20282

Cross-Section Adjustment with Monte Carlo Sensitivities: Application to the Winfrith Iron Benchmark

M. C. G. Hall

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 423-431

Technical Paper / dx.doi.org/10.13182/NSE82-A20283

Eigenvalue-Dependent Neutron Energy Spectra: Definitions, Analyses, and Applications

D. G. Cacuci, Y. Ronen, Z. Shayer, J. J. Wagschal, Y. Yeivin

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 432-442

Technical Paper / dx.doi.org/10.13182/NSE82-A20284

Particle and Radiation Leakage Importance: Definition, Analysis, and Interpretation

D. G. Cacuci, J.J. Wagschal, A. Yaari

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 443-450

Technical Paper / dx.doi.org/10.13182/NSE82-A20285

The Effects of Intracell Adjoint Flux Heterogeneity on First-Order Perturbation Reactivity Calculations

K. S. Smith

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 451-458

Technical Paper / dx.doi.org/10.13182/NSE82-A20286

An Unequal Velocity, Unequal Temperature Two-Fluid Description of Transient Vapor-Liquid Flow in Channels

Ramendra P. Roy, S. Allen Ho

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 459-467

Technical Note / dx.doi.org/10.13182/NSE82-A20287

STP: A Mathematically and Physically, Consistent Library of Steam, Properties

F. Aguilar, P. G. Tuttle, A. C. Hutter

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 467-471

Technical Note / dx.doi.org/10.13182/NSE82-A20288

Parallel Neutron Diffusion in Plane Lattices with Voids

T. Duracz

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 471-472

Technical Note / dx.doi.org/10.13182/NSE82-A20289

Neutron Diffusion in Asymmetric Cell Lattices

T. Duracz

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 472-474

Technical Note / dx.doi.org/10.13182/NSE82-A20290

On Angular Flux Computations in Neutron-Transport Theory

R. D. M. Garcia, C. E. Siewert

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 474-476

Technical Note / dx.doi.org/10.13182/NSE82-A20291

Evidence for a Time-Dependent Neutron Flux/Spectrum Anomaly at the Transient Reactor Test Facility

A. H. Lumpkin, G. J. Berzins

Nuclear Science and Engineering / Volume 81 / Number 3 / July 1982 / Pages 477-481

Technical Note / dx.doi.org/10.13182/NSE82-A20292

Number 4

Table of Contents
Fusion Plasma Analysis(J. M. Rawls)

Neutron Scattering Cross Sections for ²³²Th, ²³³U, ²³⁵U, ²³⁸U, ²³⁹Pu, and ²⁴²PU Between 0.6 and 3.4 MeV

G. Haouat, J. Lachkar, Ch. Lagrange, J. Jary, J. Sigaud, Y. Patin

Nuclear Science and Engineering / Volume 81 / Number 4 / August 1982 / Pages 491-511

Technical Paper / dx.doi.org/10.13182/NSE82-A21439

Measurement of the Neutron-Induced Fission Cross Section of ²³²Th Relative to ²³⁵U from 0.7 to 30 MeV

J. W. Behrens, J. C. Browne, E. Abies

Nuclear Science and Engineering / Volume 81 / Number 4 / August 1982 / Pages 512-519

Technical Paper / dx.doi.org/10.13182/NSE82-A21440

Technetium-99 Neutron Capture Cross Section

R. L. Macklin

Nuclear Science and Engineering / Volume 81 / Number 4 / August 1982 / Pages 520-524

Technical Paper / dx.doi.org/10.13182/NSE82-A21441

Fast Neutron Activation of 48.6-min ^111mCd in Natural Cadmium

Donald L. Smith, James W. Meadows

Nuclear Science and Engineering / Volume 81 / Number 4 / August 1982 / Pages 525-531

Technical Paper / dx.doi.org/10.13182/NSE82-A21442

Decay of Fast Neutron Pulses in Uranium Assemblies

Rajesh Mohan, Feroz Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 81 / Number 4 / August 1982 / Pages 532-539

Technical Paper / dx.doi.org/10.13182/NSE82-A21443

A Model for Effective Thermal Conductivity of Unrestructured Sphere-Pac Fuel

M. J. Ades, K. L. Peddicord

Nuclear Science and Engineering / Volume 81 / Number 4 / August 1982 / Pages 540-550

Technical Paper / dx.doi.org/10.13182/NSE82-A21444

Interference Effect of Neutron Streaming Between Different Fast Critical Assembly Cells

T. Takeda, E. Wachi

Nuclear Science and Engineering / Volume 81 / Number 4 / August 1982 / Pages 551-557

Technical Note / dx.doi.org/10.13182/NSE82-A21445

Effect of Collective and Quantum Modifications of the Energy Deposition in the Simulation of Ion Beam-Pellet Interaction

B. Levush, S. Cuperman

Nuclear Science and Engineering / Volume 81 / Number 4 / August 1982 / Pages 557-560

Technical Note / dx.doi.org/10.13182/NSE82-A21446

Determination of Fuel-Clad Thermal Gap Conductance by Use of Kalman Filter Methods

C.C. Meek, R. C. Doerner, W. J. Adams

Nuclear Science and Engineering / Volume 81 / Number 4 / August 1982 / Pages 560-562

Technical Note / dx.doi.org/10.13182/NSE82-A21447

Effective Thermal Conductivity of Sphere-Pac Fuel During Restructuring

M. J. Ades, K. L. Peddicord

Nuclear Science and Engineering / Volume 81 / Number 4 / August 1982 / Pages 563-569

Technical Note / dx.doi.org/10.13182/NSE82-A21448